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Effect of inlet throttling on thermohydraulic instability in a large scale water-based RCCS: An experimental study

Hu Rui|Ooi Zhiee Jhia|Jasica Matthew|Lisowski Darius|Lv Qiuping|Farmer Mitch
한국원자력학회 (Korean Nuclear Society)|2024.02|Nuclear Engineering and Technology|제56권 제2호|pp. 655-665|DOI 10.1016/j.net.2023.10.044

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키워드

Flow instabilityRCCSInlet throttlingNCOsDWOsGeysering
주제분류원자력공학

초록

The objective of the present experimental study is to investigate the effect of inlet throttling on the thermohydraulic stability of a large scale water-based Reactor Cavity Cooling System (RCCS). The test was performed using the water-based Natural convection Shutdown heat removal Test Facility (NSTF) at Argonne, which represented a ½ axial scale and 12.5◦ sector slice of the full scale Framatome 625 MWt SC-HTGR RCCS concept. A two-phase steady state was first established through direct condensate refill, followed by increased inlet throttling over 10 stages, corresponding to a loss coefficient K over the range of 0.05–653. With the inlet throttling gradually increased, the system experienced a unique transition process between stabilization and destabilization. Through a stability analysis, three instability mechanisms were identified in the present test, including a compound mechanism due to both natural circulation oscillations (NCOs) and density wave oscillations (DWOs), Type-II DWOs, and geysering.

Abstract

The objective of the present experimental study is to investigate the effect of inlet throttling on the thermohydraulic stability of a large scale water-based Reactor Cavity Cooling System (RCCS). The test was performed using the water-based Natural convection Shutdown heat removal Test Facility (NSTF) at Argonne, which represented a ½ axial scale and 12.5◦ sector slice of the full scale Framatome 625 MWt SC-HTGR RCCS concept. A two-phase steady state was first established through direct condensate refill, followed by increased inlet throttling over 10 stages, corresponding to a loss coefficient K over the range of 0.05–653. With the inlet throttling gradually increased, the system experienced a unique transition process between stabilization and destabilization. Through a stability analysis, three instability mechanisms were identified in the present test, including a compound mechanism due to both natural circulation oscillations (NCOs) and density wave oscillations (DWOs), Type-II DWOs, and geysering.

참고문헌 (38)

  1. Technical Letter Report: an Overview of Non-LWR Vessel Cooling Systems for Passive Decay Heat Removal, "D. Lisowski", Argonne National Laboratory, ~, pp.ANL (2021), NSE-21[DOI]
  2. Final Project Report on RCCS Testing with the Air-Based NSTF, "D. Lisowski", Argonne National Laboratory, ~, pp.ANL-ART-47 (2016)
  3. K. Fukuda, "Classification of two-phase flow instability by density wave oscillation model", J. Nucl. Sci. Technol, 16, pp.95~108 (1979)
  4. M. Furuya, "Flashing-induced density wave oscillations in a natural circulation BWR – mechanism of instability and stability map", Nucl. Eng. Des, 235, pp.1557~1569 (2005)
  5. M. Aritomi, "Fundamental study on thermo-hydraulics during start-up in natural circulation boiling water reactors, (I)thermo-hydraulic instabilities", J. Nucl. Sci. Technol, 29, pp.631~641 (1992)
  6. J. H. Chiang, "Fundamental study on thermo-hydraulics during start-up in natural circulation boiling water reactors, (II) natural circulation oscillation induced by hydrostatic head fluctuation", J. Nucl. Sci. Technol, 30, pp.203~211 (1993)
  7. J. H. Chiang, "Fundamental study on thermohydraulics during start-up in natural circulation boiling water reactors, (III) effects of system pressure on geysering and natural circulation oscillation", J. Nucl. Sci. Technol, 31, pp.883~893 (1994)
  8. C. P. Marcel, "Experimental and numerical investigations on flashing-induced instabilities in a single channel", Exp. Therm. Fluid Sci, 33, pp.1197~1208 (2009)
  9. C. P. Marcel, "Experimental investigations on flashing-induced instabilities in one and two-parallel channels : a comparative study", Exp. Therm. Fluid Sci, 34, pp.879~892 (2010)
  10. D. Lisowski, "Influences of boil-off on the behavior of a two-phase natural circulation loop", Int. J. Multiphas. Flow, 60, pp.135~148 (2014)
  11. J. A. Boure, "Review of two-phase flow instability", Nucl. Eng. Des, 25, pp.165~192 (1973)
  12. R. Uddin, "On density-wave oscillations in two-phase flows", Int. J. Multiphas. Flow, 20, pp.721~737 (1994)
  13. T. H. J. J. Van Der Hagen, "Exploring the dodewaard type-I and type-II stability; from start-up to shutd-down, from stable to unstable", Ann. Nucl. Energy, 24, pp.659~669 (1997)
  14. A. K. Nayak, "Flow instabilities in boiling two-phase natural circulation systems : a review", Science and Technology of Nuclear Installations, 2008, pp.1~15 (2008)
  15. M. Furuya, "Inlet throttling effect on the boiling two-phase flow stability in a natural circulation loop with a chimney", Heat Mass Tran, 37, pp.111~115 (2001)
  16. R. P. Mathisen, "An Experimental Study of Natural Circulation in a Loop with Parallel Flow Test Sections", AE-200, ~ (1965)
  17. Analytical Modeling and Study of the Stability Characteristics of the Advanced Heavy Water Reactor, "A. K. Nayak", Bhabda Atomic Research Center, ~, pp.BARC (2000), 2000[DOI]
  18. Y. Zhao, "Simulation investigation on flashing-induced instabilities in a natural circulation system", Ann. Nucl. Energy, 144, pp.107561~ (2020)
  19. Water-Cooled RCCS RD Designer Observation Report, "AREVA", ~, pp.Technical Data Record No.: 12-92372466-000 (2014)
  20. Water NSTF Design, Instrumentation, and Test Planning, "D. Lisowski", Argonne National Laboratory, ~, pp.ANL-ART-98 (2017)
  21. Testing with the Water-Based NSTF: Year-1 Single-phase Results, "D. Lisowski", Argonne National Laboratory, ~, pp.ANL-ART-175 (2019)
  22. Report on Year-2 of Water NSTF Matrix Testing: Two-phase Baseline &Repeatability, "D. Lisowski", Argonne National Laboratory, ~, pp.ANL-ART-206 (2020)
  23. "langed Jamesbury Ball Valves ASME Class 150 & 300 Full Bore: 1", 2"-24" (DN15-600), Series 9000, 2020, pp.B107-2EN, ~
  24. M. Furuya, "Characteristics of type-I density wave oscillations in a natural circulation BWR at relatively high pressure", J. Nucl. Sci. Technol, 42, pp.191~200 (2005)
  25. D. Papini, "On Density Wave Instability Phenomena – Modelling and Experimental Investigation", pp.257~284 (2011)[DOI]
  26. A.H. Stenning, "Flow oscillations modes in forced convection boiling", Proc. 1965 Heat Transfer and Fluid Mech. Inst, pp.301~316 (1965)
  27. M. H. Subki, "Multi parameters effect on thermohydraulic instability in natural circulation boiling water reactor during startup", JSME International Journal, 47, pp.277~286 (2004)
  28. C. Y. Wu, "Chaotic oscillations in a low pressure two-phase natural circulation loop under low power and high inlet subcooling conditions", Nucl. Eng. Des, 162, pp.223~232 (1996)
  29. F. S. Wang, "Thermal and stability analysis of a two-phase natural circulation loop", Nucl. Sci. Eng, 117, pp.33~46 (1994)
  30. Y. N. Lin, "Non-linear analysis for a natural circulation boiling channel", Nucl. Eng. Des, 152, pp.349~360 (1994)
  31. D. D. B. Van Bragt, "Stability of natural circulation boiling water reactors : Part I – description stability model and theoretical analysis in terms of dimensionless groups", Nucl. Technol, 121, pp.40~51 (1998)
  32. D. D. B. Van Bragt, "Stability of natural circulation boiling water reactors : Part II – parametric study of coupled neutronic-thermohydraulic stability", Nucl. Technol, 121, pp.52~62 (1998)
  33. M. Furuya, "Density wave oscillations of a boiling natural circulation loop induced by flashing", Proc. 7th Int. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-7) (1995)
  34. S. Y. Jiang, "Analysis of flow oscillations in a natural circulation system taking account of non-equilibrium boiling and void flashing", Kerntechnik, 61, pp.23~ (1996)
  35. S. Shi, "Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor", Ann. Nucl. Energy, 101, pp.215~225 (2017)
  36. S. Nakanishi, "Flow instability in boiling channels : 2 geysering", Trans. JSME J. Heat Transfer, 44, pp.4252~4262 (1978)
  37. C. Tompkins, "Flow pattern transition instabilities in a natural circulation cooling facility", Nucl. Eng. Des, 332, pp.267~278 (2018)
  38. D. D. Lisowski, "Influences of boil-off on the behavior of a two-phase natural circulation loop", Int. J. Multiphas. Flow, 60, pp.135~148 (2014)

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